ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Yean-Chuan Yeh, Jyh-Tong Teng
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 252-255
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34207
Articles are hosted by Taylor and Francis Online.
A quantified correlation process to assess those dynamic human error probabilities for which timing data can be sampled from generic occurrences and/or from plant-specific simulator training records is presented. The method is based on a comparison between two random variables, representing the critical time for system response and the action time for operator achievement capability. The maximum entropy estimator is employed to handle the sampled timing data. The operator action in performing rapid cooldown and depressurization following an initiating event of steam generator tube rupture is used to delineate this method. The resulting datum has been successfully applied in a risk analysis project.